ML081820203

Enclosure 2, Markup of Proposed Technical Specifications

ML081820203
Person / Time
Site:	Vogtle
Issue date:	06/27/2008
From:	Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML081820193	List: ML081820196 ML081820203 ML081820208 ML081820210 ML081820214 ML081820216 ML081820219 ML081820223 NL-08-0869, Enclosure 11, List of Regulatory Commitments NL-08-0869, Vogtle, Units 1 and 2 - Enclosure 2, Markup of Proposed Technical Specifications NL-08-0869, Vogtle, Units 1 and 2 - Enclosure 3, Typed Pages for Technical Specification NL-08-0869, Vogtle, Units 1 and 2 - Enclosure 4, Westinghouse Letter, CAW-08-2449, Application for Withholding and Affidavit, Proprietary Information Notice, and Copyright Notice NL-08-0869, Vogtle, Units 1 and 2 - Enclosure 5, Westinghouse Electric Company LLC, LTR-CDME 08-11-NP, Interim Alternate Repair Criterion (ARC) for Cracks in the Lower Region of the Tubesheet Expansion Zone, Dated January 31, 2008 (Non-Proprietary) NL-08-0869, Vogtle, Units 1 and 2 - Enclosure 7, Westinghouse Letter, CAW-08-2448, Application for Withholding and Affidavit, Proprietary Information Notice, and Copyright Notice NL-08-0869, Vogtle, Units 1 and 2 - Enclosure 8, Westinghouse Electric Company LLC, LTR-CDME-08-043 NP-Attachment, Response to NRC Request for Additional Information Relating to LTR-CDME-08-11 NP-Attachment, Dated March 18, 2008
References
NL-08-0869
Download: ML081820203 (3)

Text

VogUe Electric Generating Plant Units 1 and License Amendment Request to Revise Technical Specification Sections 5.5.9, "Steam Generator (SG) Program" and TS "Steam Generator Tube Inspection Report" for Interim Alternate Repair Enclosure Markup of Proposed Technical

5.5.9 Programs

and Manuals 5.5 5.5 Programs and Manuals Steam Generator (SG) Program (continued) Accident induced leakage performance criterion:

The primary to secondary accident induced leakage rate for any design basis accident, other than a SG tube rupture, shall not exceed the leakage rate assumed in the accident analysis in terms of total leakage rate for all SGs and leakage rate for an individual SG. Leakage is not to exceed 1 gpm per SG. The operational LEAKAGE performance criterion is specified in LCO 3.4.13, "RCS Operational LEAKAGE." Provisions for SG tube repair criteria.

Tubes found by inservice inspection to contain flaws with a depth equal to or exceeding 40% of the nominal tube wall thickness shall be plugged. The following alternate tube repair criteria shall be applied as an alternative to the 40% depth based criteria: For Unit 2 during Refueling Outage 11 and the subsequent operating cycle, degradation found in the portion of the tube below 17 inches from the top of the hot leg tubesheet does not require plugging.

For Unit 2 during Refueling Outage 11 and the subsequent operating cycle, degradation identified in the portion of the tube from the top of the hot leg tubesheet to 17 inches below the top of the tubesheet shall be plugged upon detection. For Unit 1 during Refueling Outage 13 and the subsequent operating cycle, and for Unit 2 during Refueling Outage 12 and the subsequent operating cycle, degradation identified in the portion of the tube below 17 inches from the top of the hot leg tubesheet does not require plugging.

For Unit 1 during Refueling Outage 13 and the subsequent operating cycle, and for Unit 2 during Refueling Outage 12 and the subsequent operating cycle, degradation identified in the portion of the tube from the top of the hot leg tubesheet to 17 inches below the top of the hot leg tubesheet shall be plugged upon detection. For Unit 1 during Refueling Outage 14 and the subsequent operating cycle and 2 dulJOO RefuelU1g, I 1 J and the sub nl Q12'" atinCLC-'i.cJ..e, tubes with flaws having a circumferential component less than or equal to 203 degrees found in the portion of the tube below 17 inches from the top of the tubesheet and above 1 inch from the bottom of the tubesheet do not require plugging.

Tubes with flaws having a (continued)

Vogtle Units 1 and 2 Amendment No. +W (Unit 1) Amendment No. +3Q (Unit 2)

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.9 Deleted. 5.6.10 Steam Generator Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with the Specification 5.5.9, Steam Generator (SG) Program. The report shall include: The scope of inspections performed on each SG, Active degradation mechanisms found, Nondestructive examination techniques utilized for each degradation mechanism, Location, orientation (if linear), and measured sizes (if available) of service induced indications, Number of tubes plugged during the inspection outage for each active degradation mechanism, Total number and percentage of tubes plugged to date, The results of condition monitoring, including the results of tube pulls and in-situ testing, Following completion of a Unit 1 inspection performed in Refueling Outage 14 (and any inspections performed in the subsequent operating cycle) and tollowlQQ d Unit 2 Inspection Outage 1 l! 110 PQIIQ med mJJ Ie the number of indications and location, size, orientation, whether initiated on primary or secondary side for each service-induced flaw within the thickness of the tubesheet, and the total of the circumferential components and any circumferential overlap below 17 inches from the top of the tubesheet as determined in accordance with TS 5.5.9.c.3; Following completion of a Unit 1 inspection performed in Refueling Outage 14 (and any inspections performed in the subsequent operating cycle) j.\!1.0 ompletlQn oj a actl Qrm.e.d III R9fu__

Jrl lie subse-&l.,ten1 operating the primary to secondary LEAKAGE rate observed in each SG (if it is not practical to assign leakage to an individual SG, the entire primary to secondary LEAKAGE should be conservatively assumed to be from one SG) during the cycle preceding the inspection which is the subject of the report; and Following completion of a Unit 1 inspection performed in Refueling Outage 14 (and any inspections performed in the subsequent operating cycle)

Unit 2 lospecllooQ,e,-orrned In

'lnd any perforrne..d In w..Qseauenl gp-e atloq cycle), the calculated accident leakage rate from the portion of the tube below 17 inches from the top of the tubesheet for the most limiting accident in the most limiting SG. Vogtle Units 1 and 2 5.6-6 Amendment No. 4-W (Unit 1) Amendment No. -l-3Q (Unit 2)